Updated on 2025/03/14

写真a

 
UMEKAWA,Hisashi
 
Organization
Faculty of Engineering Science Professor
Title
Professor
Contact information
メールアドレス
External link

Degree

  • Doctor of Engineering ( 1998.9 )

  • Master of Engineering ( 1988.3 )

Research Areas

  • Manufacturing Technology (Mechanical Engineering, Electrical and Electronic Engineering, Chemical Engineering) / Thermal engineering

Education

  • Kansai University   Graduate School, Division of Engineering

    1988

      More details

    Country: Japan

    researchmap

  • Kansai University   Faculty of Engineering

    - 1986

      More details

    Country: Japan

    researchmap

Professional Memberships

Committee Memberships

  • 日本混相流学会   混相流計測技術国際シンポジウム委員会委員  

    2023.7   

      More details

  • 日本機械学会   年次大会企画委員会委員長  

    2023 - 2025   

      More details

  • 日本混相流学会   監事  

    2023 - 2025   

      More details

  • 日本混相流学会   研究企画委員会相変化を伴う混相流の熱流動主査  

    2022   

      More details

  • 日本機械学会   関西支部企画幹事長  

    2020 - 2021   

      More details

  • 日本機械学会   2018年度年次大会実行委員会委員長  

    2018.9   

      More details

  • 日本伝熱学会   関西支部担当理事  

    2016.5 - 2018.4   

      More details

    Committee type:Academic society

    researchmap

  • 日本伝熱学会   関西支部副支部長  

    2016.4 - 2018.3   

      More details

  •   動力エネルギーシステム部門長  

    2015.4 - 2016.3   

      More details

  • 日本混相流学会   副会長  

    2013.8 - 2015.7   

      More details

  •   評議員  

    2013.6 - 2023   

      More details

  • 日本混相流学会   編集委員長  

    2012.8 - 2014.7   

      More details

▼display all

Papers

  • Evaluation of subcooled void fraction in downward flow under low mass flux condition by using neutron radiography Reviewed

    Takeyuki Ami, Hisashi Umekawa, Daisuke Ito, Yasushi Saito

    EXPERIMENTAL THERMAL AND FLUID SCIENCE   141, 110799   2023.2

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE INC  

    In downward flow, complex two-phase flow is caused by buoyancy of bubbles. It affects not only a void fraction profile but also a point of net vapor generation (PNVG). In order to understand the fundamental characteristics of the void fraction on subcooled boiling in downward flow, the void fraction was measured by using neutron radiography. The test sections were made of stainless steel tubes that had 400 mm in heated length with 10 and 15 mm in inner diameters. They were heated by direct Joule heating applying D.C. power. The void fraction characteristics were explained by dividing into three regions: i.e., a wall voidage region, a detached voidage region, and a bulk voidage region. PNVG was defined as the boundary between the detached voidage region and the bulk voidage region. In a downward flow, the thermal equilibrium quality at PNVG is smaller than in an upward flow. "Secondary PNVG" was also observed which was caused by the influence of a reverse flow of bubbles. A difference of thermal equilibrium quality between at primary PNVG and at secondary PNVG is lager in 15 mm in inner diameter than in 10 mm. The void fraction profile and PNVG characteristics in downward flow show dependence of inner diameter as well as mass flux. To demonstrate the void fraction profile involving with the influence of a reverse flow in a downward flow, an empirical void fraction correlation based on a drift-flux model with Lahey's flow quality model was developed. This correlation well agreed with the experimental results.

    DOI: 10.1016/j.expthermflusci.2022.110799

    Web of Science

    researchmap

  • 垂直下降流における沸騰開始点の特性 Reviewed

    亀田 貴俊(D), 網 健行, 梅川 尚嗣

    日本機械学会論文集   Vol.86 No.883   2020

  • DYNAMIC SIMULATION OF PRESSURE DROP OSCILLATION IN GAS–LIQUID TWO-PHASE FLOW SYSTEM Reviewed

    Takeyuki Ami, Mayuho Kitagawa, Hisashi Umekawa, Mamoru Ozawa

    Multiphase Science and Technology   31・1-16   2019

     More details

  • DYNAMIC SIMULATION OF PRESSURE DROP OSCILLATION IN GAS–LIQUID TWO-PHASE FLOW SYSTEM Reviewed

    Takeyuki Ami, Mayuho Kitagawa, Hisashi Umekawa, Mamoru Ozawa

    Multiphase Science and Technology   31・1-16   2019

  • DYNAMIC SIMULATION OF PRESSURE DROP OSCILLATION IN GAS–LIQUID TWO-PHASE FLOW SYSTEM Reviewed

    Takeyuki Ami, Mayuho Kitagawa(D), Hisashi Umekawa, Mamoru Ozawa

    Multiphase Science and Technology   31・1-16   2019

     More details

  • Prediction Model of Critical Heat Flux for Vertical Downward Flow Reviewed

    Yoshiki Kawazoe, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    Transaction of the JSME   84(859)   2018.3

  • Flow Characteristics of Counter-current Two-ohase Flow in Structured Packings -Influence of Clearance of Packings- Reviewed

    Takehiro Kubota, Takeyuki Ami, Hisashi Umekawa

    Japanese Journal of Multiphas Flow   30(5)   2017.3

  • The Influence of the Heating Condition on the Void Fraction of Boiling Channel Reviewed

    Hisashi UMEKAWA, Syota Nakamura(D), Syota Fujiyoshi(D), Takeyuki Ami, Mamoru OZAWA, Yasusi Saito(KURRI), Daiskue Ito(KURRI)

    Physics Procedia   Vol.69, 599-606   599 - 606   2015.9

     More details

    Publishing type:Research paper (international conference proceedings)  

    © 2015 The Authors. The void fraction profile in a boiling channel is essential in analyzing convective flow boiling, where several investigations have been conducted. But due to the difficulty in the treatment of the non-thermodynamic equilibrium phenomena under subcooled conditions, the issues in comprehensive void fraction profile has not been solved, yet. To improve the understanding of these phenomena, detailed measurement results are required. In this investigation, by using five kinds of test sections, i.e. I.D.=3 mm L=400 mm, I.D.=5 mm L=200, 400, 1000 mm, and I.D.=10 mm L=400 mm, the void fraction was measured quantitatively over the whole length. For the measurements, thermal neutron radiography at the B-4 port of the Kyoto University Research Reactor was used. This facility is designed for the visualization of forced convective flow boiling in vertical tubes. To introduce the performance of this facility, this paper presents the measurement results of void fraction and the estimation results briefly.

    DOI: 10.1016/j.phpro.2015.07.085

    Scopus

    researchmap

  • The Influence of the Heating Condition on the Void Fraction of Boiling Channel

    Hisashi UMEKAWA, Syota Nakamura(D, Syota Fujiyoshi(D, Takeyuki Ami, Mamoru OZAWA, Yasusi Saito(KURRI, Daiskue Ito(KURRI

    Physics Procedia   Vol.69, 599-606   2015.9

  • Influence of tube diameter on critical heat flux in downward flow, Reviewed

    Takeyuki Ami, Takayuki Harada, Hisashi Umekawa, Mamoru Ozawa

    Multiphase Science and Technolog   27(1)77-97 ( 1 )   77 - 97   2015

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Begell House Inc.  

    Critical heat flux (CHF) is one of the key design factors for boiling heat transfer equipment. Thus, CHF, especially under upward flow condition, has been widely investigated, but the characteristics of CHF for downward flow are quite different from for upward flow. In downward flow, the complex flow structure is formed due to the counter force between the buoyancy and inertia. In view of thermal-hydraulic characteristics, downward flow should be avoided in boiling equipment. However, in a research reactor, downward flow is applied as a simplified cooling method of the reactor core. The objective of this investigation is to grasp the influence of the tube diameter on CHF in downward flow, because CHF in downward flow is closely related to the flow structure, which is influenced by the diameter and the flow velocity. The CHF experiment was carried out with a forced convective boiling system by using various inner diameter tubes in upward and downward flows. On the basis of the obtained pressure drop of the test section, behavior of inlet fluid temperature, and the location of CHF, the experimental CHF could be classified into four modes, i.e., complete dryout of falling liquid film, CHF due to flooding, CHF caused by hydraulic instability, and liquid film dryout in annular flow. These CHF are discussed by using the CHF model based on the regime-based modelling.

    DOI: 10.1615/MultScienTechn.v27.i1.50

    Scopus

    researchmap

  • Investigation of Water Behavior in Defrosting Process by Using Neutron Radiography

    MATSUMOTO Ryosuke, YOSHIMURA Tomoya, UMEKAWA Hisashi, AMI Takeyuki, ITO Daisuke, SAITO Yasushi

    Transactions of the Japan Society of Refrigerating and Air Conditioning Engineers   32 ( 4 )   419 - 426   2015

     More details

    Language:Japanese   Publisher:Japan Society of Refrigerating and Air Conditioning Engineers  

    The frost layer with melting water was measured by using a neutron radiography in the defrosting process on the aluminum finned-tube heat exchanger under the forced-convection. The water deposition distributions were estimated quantitatively in every 5 seconds for 10 minutes of the defrosting period. The melting water behavior was investigated by comparing the water deposition distribution before defrosting. The initial stage of the defrosting was referred to as the melting progressing period, in which the melting water penetrated into the water permeation layer in the frost thickness direction. The melting water penetration into the spanwise direction of the fins was not observed by the neutron radiography. After 180sec from starting the defrosting process, the frost at the fin front edge and the surrounding the tubes were melted, then, the water permeation layer was saturated by the melting water. The neutron radiography images indicated the melting water penetration into the spanwise direction of the fins. The total migration volume of the melting water into the spanwise direction was about 30% of the total frost deposition.

    DOI: 10.11322/tjsrae.15-29_OA

    researchmap

  • Dryout of counter-current two-phase flow in a vertical tube

    Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    INTERNATIONAL JOURNAL OF MULTIPHASE FLOW   67   54 - 64   2014.12

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:PERGAMON-ELSEVIER SCIENCE LTD  

    Dryout of counter-current two-phase flow is one of key issues in chemical and/or industrial systems. The aim of the present study is to provide insights into the dryout phenomena of such counter-current two-phase flow of binary gas and liquid in a vertical tube. Experimental results suggest a significant influence of the subcooling of water and the binary gas flow rate on the dryout characteristics. The observed dryout was classified into three modes, i.e.,film breakdown, dryout due to flooding and dryout due to critical flooding. At the low inlet air flow rate, dryout characteristics wereaffected by subcooling of water. The test section was partially overheated owing to the liquid film breakdown due to the Marangoni effect. At the moderate inlet air flow rate, the dryout is induced by the reduction on the falling liquid film due to flooding. At the high gas flow rate, most of the water was carried over due to the critical flooding. In the latter two cases, there was no influence of subcooling of water on dryout. These dryout phenomena were successfully realized in the numerical simulation based on the one-dimensional heat and mass transfer model, i.e., energy balance of a heat input, a heat release rate from the heating surface and a mass transfer rate due to phase change. (C) 2014 Elsevier Ltd. All rights reserved.

    DOI: 10.1016/j.ijmultiphaseflow.2014.09.002

    Web of Science

    researchmap

  • Influence of the Flow Pattern on Critical Heat Flux Reviewed

    Goshi Yamashina, Noriko Nakamura, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA

    Japanese Journal of Multiphase Flow   Vol.27 No.5 ( 5 )   571 - 576   2014.3

     More details

    Language:Japanese  

    CiNii Books

    researchmap

  • CHF in a Circumferentially Nonuniformly Heated Tube Under Low-Pressure and Low-Mass-Flux Condition (Influence of Inclined Angles Under High-Heat-Flux Condition)

    Takeyuki Ami, Takuya Hirose, Noriko Nakamura, Hisashi Umekawa, Mamoru Ozawa

    HEAT TRANSFER ENGINEERING   35 ( 5 )   430 - 439   2014.3

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:TAYLOR & FRANCIS INC  

    Critical heat flux (CHF) is an important design factor for boiling two-phase flow equipment, such as boilers and others. In actual boiling systems, the water tube suffers from the nonuniform heating and/or tube inclinations. The objective of this investigation is to understand the influence of tube inclination on CHF characteristics under such high-heat-flux conditions. The experimental investigation was conducted with a forced convective boiling system by using a uniformly heated tube and a nonuniformly heated tube set at arbitrary inclination angles phi. The obtained CHF was strongly influenced by the circumferential location of local maximum heat flux point and tube inclination. In the case of the normal tube, the CHF always occurred by the liquid film dryout at the top of the tube. In the case of the nonuniformly heated tube, the influence of the inclination on the CHF characteristics strongly depended on the circumferential heat flux distribution. When the the heat flux at the bottom was higher than that at the top, two types of CHF mechanism, namely, low-quality CHF upstream of the test section under high-mass-flux condition, and liquid film dryout at the tube exit under low-mass-flux condition, were observed. When the heat flux at the top was higher than that at the bottom, intermittent dryout was observed as the dryout mechanism. These CHF characteristics could be categorized by using the CHF ratio against the value of the vertical upward flow with the modified Froude number, which corresponded to the influence factor of disturbance wave.

    DOI: 10.1080/01457632.2013.832581

    Web of Science

    researchmap

  • Estimation of Frost Formation by using Neutron Radiography:-Estimation of Frost Deposition and Mass Transfer Coefficient on Cold Flat Plate-

    MATSUMOTO Ryosuke, YOSHIMURA Tomoya, UMEKAWA Hisashi, AMI Takeyuki, ITO Daisuke, SAITO Yasushi

    Transactions of the Japan Society of Refrigerating and Air Conditioning Engineers   31 ( 2 )   207 - 217   2014

     More details

    Language:Japanese   Publisher:Japan Society of Refrigerating and Air Conditioning Engineers  

    Frost formation on heat exchangers can have a serious impact on their heat transfer performance due to the thermal resistance and pressure drop by the frost layer. Many studies had been carried out to investigate frosting on a flat plate, cylindrical surface and heat exchangers. In conventional methods of measuring the frost formation, the frost is scraped from the surface, making the temporal and spatial distributions of its frost deposition difficult to determine. In the present study, the frost formation on a cold flat plate is investigated by using neutron radiography. Neutrons are strongly attenuated by the water molecules in the frost layer, but not by the aluminum cold flat plate. The frost formation can be quantitatively estimated based on neutron beam attenuation. The mass attenuation coefficient of water to the neutron beam is estimated by the calibration test using the phantom piece. Frost formation and growth on the cold flat plate could be clearly measured by neutron radiography. The frost deposition was measured every 10 min, so that the local frost accumulation rate could be estimated from differential images. The spatial and temporal distributions of the local mass transfer coefficient could be successfully measured using neutron radiography.

    DOI: 10.11322/tjsrae.31.207

    CiNii Books

    researchmap

  • Characteristics of Trailing Bubble Velocity in Consecutive Large Bubbles Rising through a Inclined Tube Reviewed

    Noriko Nakamura, Yoshimune Hirose, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA

    Japanese Journal of Multiphase Flow   Vol.27 No.3 306-315 ( 3 )   306 - 315   2013.9

     More details

    Language:Japanese   Publisher:THE JAPANESE SOCIETY FOR MULTIPHASE FLOW  

    In this study, the rising velocity of Taylor bubbles in inclined tube was investigated. In the experiment, the air-water two-phase flow system equipped with the Taylor bubble injector, which can inject arbitrary size Taylor bubble with a certain distance, was used. The inclined angle was 30-90 degree, the tube inner diameter was 20mm, the dimensionless bubble diameter λ was 0.6-2.0 and liquid velocity was 0.011-0.053m/s. As the result, the influence of the tube inclination and bubble size on the correlation for the bubble velocity with the separation distance of two consecutive bubbles was presented. On the basis of these results, the characteristics of the Taylor bubble movements were explained. Moreover, the fundamental data of two consecutive bubbles, i.e. the maximum trailing bubble velocity, the location of maximum velocity, the effective range of velocity and the damping ratio of velocity were reported.

    DOI: 10.3811/jjmf.27.306

    CiNii Books

    researchmap

    Other Link: https://jlc.jst.go.jp/DN/JALC/10024372359?from=CiNii

  • Pseudo dynamic visualization of boiling two-phase flow under oscillatory flow condition

    H. Umekawa, T. Ami, S. Fujiyoshi, Y. Saito

    Physics Procedia   43   269 - 276   2013

     More details

    Language:English   Publishing type:Research paper (international conference proceedings)   Publisher:Elsevier B.V.  

    Although the flow oscillation strongly affects the characteristic of the critical heat flux, the detailed feature of these phenomena had not been fully understood, so far. One of the reasons of the lack of the reports is owing to the characteristics of the flow oscillation, i.e. the flow oscillation is strongly influenced by the operating condition. This means the oscillatory condition changes by the heating condition, thus general discussion becomes difficult. In this series of investigations, the critical heat flux (CHF) was investigated under artificial flow oscillation generated by a mechanical flow oscillator. By using these means, the influence of the flow oscillation was systematically obtained, and several results and model were presented. In this investigation, the similar experimental investigation was conducted to estimate the dynamic movement of the void fraction. In the visualization procedure, 0.03 second exposure image which synchronized with the flow oscillator was taken, and by using the ensemble averaging of 34 images, the image which had enough dynamic range could be reconstructed. © 2013 The Authors. Published.

    DOI: 10.1016/j.phpro.2013.03.031

    Scopus

    researchmap

  • Flow Characteristics of Oil-Water Mixture in Horizontal Mini-Channel (Influence of Inner Diameter and Geometry of Mixer) Reviewed

    AMI Takeyuki, Kouhei Awata, Hisashi Umekawa, Mamoru Ozawa

    Japanese Journal Multiphase Flow   Vol.26No.3, 302-311 ( 3 )   302 - 311   2012.9

     More details

    Language:Japanese   Publisher:THE JAPANESE SOCIETY FOR MULTIPHASE FLOW  

    Immiscible two components flow is widely observed in several engineering equipments such as pipeline, μ-TAS and so on, and it has been also utilized as the simulation of the two-phase flow under high pressure conditions. However, the knowledge of fluid characteristics in mini-channel is still not enough, especially the influence of the methods of the mixing is not clear. In order to clarify the flow characteristic of oil-water mixture in horizontal mini-channels, the experimental investigation was conducted by using a forced convective flow system with two different mixers with two mixing manners. The test section was made of glass tube with 0.53mm and 2.09 mm in inner diameter. As the experimental results, the several flow patterns were identified and flow pattern transition was correlated by using Weber number of each phase. The pressure drop for 2.09 mm took the characteristics of ordinary tube, while 0.53 mm took the typical characteristics of capillary tube. The obtained pressure drop showed a good agreement with Lockhart-Martinelli correlation.

    DOI: 10.3811/jjmf.26.302

    CiNii Books

    researchmap

    Other Link: https://jlc.jst.go.jp/DN/JALC/10009862219?from=CiNii

  • Critical Heat Flux in a Circumferentially Non-Uniformly Heated Tube (Influence of Inclined Angles under High flux conditions) Reviewed

    Japanese Journal of Multiphase Flow   Vol.25No.2 178-191   2012.6

     More details

  • Influence of a Flow Obstacle on Boiling Two-Phase Flow Reviewed

    Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    Transactions of Japan Society of Mechanical Engineers Ser. B.   Vol.78 No.788 pp.894-904   727 - 734   2012.4

     More details

    Language:English   Publishing type:Research paper (international conference proceedings)   Publisher:AMER SOC MECHANICAL ENGINEERS  

    The spacer of Boiling Water Reactor (BWR) becomes the flow obstacle. Moreover the clearance between fuel rods of the innovative Water Reactor for Flexible fuel cycle (FLWR) becomes very narrow. Thus understanding of the thermal-fluid characteristics in the boiling channel equipped with the flow obstacle becomes more important. In this study, to clarify the flow obstacle effect, the experimental investigation was conducted with the forced convective boiling system. The test section was 8 mm in inner diameter, and the rod-type flow obstacle, which had 3.6 mm in diameter and 20 mm in length, was installed. The blockage ratio beta = 20.3 % which was the similar value of the present BWR reactor. The heating length L-T was taken three different lengths, L-T = 810, 840 and 900 mm As the experimental results, the CHF was increased by the installing of the flow obstacle, and it was strongly influenced by the axial position of the flow obstacle. In the most of the case, the liquid film dryout was detected at the exit of the test section, while the CHF was observed at the upstream of the flow obstacle in the case of the L-T = 810 mm. The calculation results of the liquid film flow model have shown a good agreement with these experimental results by using the presented influence length of the flow obstacle.

    Web of Science

    researchmap

  • Flow Pattern and Boiling Heat Transfer of CO2 at High Pressure in Horizontal Mini-Channels Reviewed

    AMI Takeyuki, NAKAMURA Noriko(D), UMEKAWA Hisashi, OZAWA Mamoru, SHOJI Masaharu(Kanagawa Univ.)

    Int. Heat Transfer Conference   IHTC14-22560   2011.8

     More details

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束 加熱熱流束の影響について Reviewed

    網健行, 梅川尚嗣, 小澤守, 三島嘉一郎, 齊藤泰司

    日本機械学会論文集(B編)   Vol.77 No.7781385-1396   2011.6

     More details

  • 小口径管におけるフラッディング 供試管材質の影響 Reviewed

    西本貴明(D), 民谷 尚紀(B), 網 健行, 梅川 尚嗣, 小澤 守

    日本機械学会論文集(B編)   Vol.77No.776 1011-1015   2011.4

     More details

  • 連続スラグ気泡の相互干渉に関する評価 Reviewed

    中村典子, 網健行, 梅川尚嗣, 小澤守

    混相流   Vol.24 No.5 549-557   2011.3

     More details

  • らせん管内液体窒素沸騰二相流における伝熱・流動特性 Reviewed

    網 健行, 中村典子, 鶴野嵩敬, 樋口 徹, 梅川尚嗣, 小澤守

    混相流   Vol.24 No.5 567-576   2011.3

     More details

  • Critical Heat Flux in a Circumferentially Non-Uniformly Heated Tube under Low Pressure and Low Mass Flux Condition (Inclined upward flow)

    AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru, MISHIMA Kaichiro, SAITO Yasushi

    Heat Transfer Asian Research   Vol.40No.2,125-139 ( 2 )   125 - 139   2011.3

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    Critical Heat Flux (CHF) in a non-uniformly heated tube is a very important design factor of actual boiling equipment. In this series of studies, the CHF in a non-uniformly heated tube has been evaluated by considering the re-distribution of a liquid film caused by the wave interaction. In the present investigation, in order to estimate the influence of the magnitude of the heat flux, the CHF experiment was conducted. The experimental apparatus was the same as the forced convective boiling system presented in the previous paper, i.e. the eccentric tube with 20 mm I.D., 24 mm O.D., but heated length was just only 450 mm to keep the high heat flux condition. The experimental result indicated the influence of the magnitude of the heat flux as the entrainment increased. In this investigation, two kinds of the CHF mechanisms were observed, i.e. liquid film dryout at the high quality condition and departure from nucleate boiling (DNB) at the low quality condition, respectively. This obtained CHF has been evaluated by using the film flow model, and the empirical correlation of the spreading coefficient of liquid film re-distribution was proposed.

    DOI: 10.1002/htj.20333

    Scopus

    researchmap

  • CHF in a circumferentially nonuniformly heated tube under low-pressure and low-mass-flux condition

    AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru, MISHIMA Kaichiro, SAITO Yasushi

    Heat Transfer -Asian Research   Vol.40 No.2 125-139   2011.3

     More details

  • Forced Flow Boiling of Carbon Dioxide in Horizonta Mini-Channel Reviewed

    OZAWA Mamoru, AMI Takeyuki, UMEKAWA Hisashi, MATSUMOTO Ryosuke, HARA Takashi

    Int. J. Thermal Science   Vol.50 296-308   2011.1

     More details

  • Critical Heat Flux Induced by Flow Instability in Boiling Channels - A review Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MATSUMOTO Ryosuke, AMI Takeyuki

    Nuclear Safety and Simulation   Vol.2 No.1 104-120   2010.6

     More details

  • The Prediction of the Dryout under Flooding Condition in a Small Diameter Tube Reviewed

    NISHIMOTO Takaaki, AMI Takyuki, UMEKAWA Hisashi, OZAWA Mamoru

    Japanese Journal of Multiphase Flow   Vol.23 No.5 ( 5 )   563 - 570   2010.3

     More details

    Language:Japanese  

    CiNii Books

    researchmap

  • Flow Boiling in Horizontal Mini-Channels: Flow Pattern of CO2 at High Pressure Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, AMI Takeyuki, MATSUMOTO Ryosuke, HARA Takashi

    Multiphase Science and Technology   Vol.22No.2 115-132 ( 2 )   115 - 132   2010

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    This paper describes the flow patterns of carbon dioxide two-phase flow at high pressure observed in horizontal minichannels ranging from 0.51 to 3.0 mm in diameter, together with the flow pattern maps and related boiling heat-transfer characteristics. The observed flow patterns are mainly classified into bubbly, slug, slug-annular, and annular flows, similar to conventional pipes, while phase stratification tendency is still significant even in a 1.0 mm tube, so that heat transfer at high pressure shows significant differences in the upper and lower walls, especially in 2.0 and 3.0 mm tubes. Such phase stratification with reference to heat transfer is roughly scaled by means of boiling number and Bond number. The newly developed simulation model by the authors for conventional-sized tubes is successfully applied to 2.0 and 3.0 mm pipes, but not to 0.51 and 1.0 mm tubes. This model suggests that thermal flow behavior at higher Bond number Bo than 8.2 is similar to that of conventional-sized tube, and cases less than Bo = 8.2 show minichannel behavior. The heat transfer in these minichannels is well-predicted with Schrock-Grossman type correlation with nucleate and forced-convective effects, while in larger tubes, e.g., 2.0 and 3.0 mm, the heat transfer is mainly dominated by nucleate boiling in the present experimental ranges. © 2010 by Begell House, Inc.

    DOI: 10.1615/MultScienTechn.v22.i2.20

    Scopus

    researchmap

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束傾斜上昇流におる傾斜角の影響について Reviewed

    網健行, 梅川尚嗣, 小澤守, 三島嘉一郎, 齋藤泰司

    日本機械学会論文集(B編)   Vol.75 No.751 474-475   2009

     More details

  • Flow Pattern and Boiling Heat Transfer of CO2 in Horizontal Small-Bore Tubes Reviewed

    OZAWA Mamoru, AMI Takeyuki, ISHIHARA Isao, UMEKAWA Hisashi, MATSUMOTO Ryosuke, TANAKA Yasuhiko, YAMAMOTO Taku, UEDA Yuya

    International Journal of Multiphase Flow   Vol.35 699-709 ( 8 )   699 - 709   2009

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:PERGAMON-ELSEVIER SCIENCE LTD  

    Increasing attention has been focused on carbon dioxide (CO2) heat Pump system where the temperature level is rather low, while the operating pressure is rather high. in this system, the density difference between vapor and liquid becomes rather small, which significantly affects flow patterns. Low tension and latent heat also have significant influence on two-phase flow patterns and heat transfer. This paper describes experimental and numerical investigation on flow patterns and heat transfer characteristics of boiling flow CO2 at high pressure in horizontal small-bore tubes ranging from 1.0 mm to 3.0 mm I.D. Even though the density difference is rather small at high pressure, phase stratification takes place, which leads to the intermittent dryout at the upper wall. So far developed discrete bubble model by the authors for vertical flows is modified so as to include horizontal flow mechanisms. The predicted flow patterns with this new model agree on the whole with the experimental observation. (C) 2009 Elsevier Ltd. All rights reserved.

    DOI: 10.1016/j.ijmultiphaseflow.2009.04.003

    Web of Science

    researchmap

  • Traveling void wave in horizontal two-phase flow Reviewed

    AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru, SHOJI Masahiro

    International Journal of Heat and Mass Transfer   Vol52 No.25-26 5682-5690 ( 25-26 )   5682 - 5690   2009

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:PERGAMON-ELSEVIER SCIENCE LTD  

    In the framework of pattern dynamics approach, the discrete bubble model was developed for simulating inherent fluctuation of void fraction in a horizontal two-phase flow. Then flow patterns were identified based on the statistical properties of void fraction fluctuation, and the flow pattern map agreed with the experimental observation of high-pressure two-phase flow Of CO(2) in horizontal tubes. The time-averaged pressure drop and the void fraction obtained in the simulation agreed reasonably with the existing correlations. Thus the horizontal flow version of the discrete bubble model demonstrates its relevance in simulating inherent fluctuation of two-phase flow. (C) 2009 Elsevier Ltd. All rights reserved.

    DOI: 10.1016/j.ijheatmasstransfer.2009.08.018

    Web of Science

    researchmap

  • Heat Transfer and Flow Characteristics around a Finned-Tube Bank Heat Exchanger in Fluidized-bed Reviewed

    HONDA Ryosuke, UMEKAWA Hisashi, OZAWA Mamoru

    Nuclear Instruments and Methods in Physics Research -A   Vol.605 188-191 ( 1-2 )   188 - 191   2009

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE BV  

    Principal heat transfer mechanisms in a fluidized bed have been classified into three categories, i.e. solid convection, gas convection and radiation. Among these mechanisms, the solid convection is a dominant mechanism in the bubbling fluidized bed. This solid convection is substantially caused by the bubble movement, thus the visualization of the void fraction distribution becomes a very useful method to understand the characteristics of the fluidized-bed heat exchanger. In this study, the heat transfer coefficient and the void fraction around the heat transfer tube with annuler fin were measured. For the quantitative measurement of the void fraction, neutron radiography and image processing technique were employed. Owing to the existence of the annuler fin, the restriction of the particle movements was put. This restriction suppressed the disturbance caused by tubes, and the influence of the tube arrangement on the flow and heat transfer characteristics could be clearly expressed. (C) 2009 Elsevier B.V. All rights reserved.

    DOI: 10.1016/j.nima.2009.01.151

    Web of Science

    researchmap

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束 傾斜上昇流の場合 Reviewed

    網 健行, 梅川尚嗣, 小澤守, 三島嘉一郎, 齋藤泰司

    日本機械学会論文集(B編)   Vol.75 No.7581903-1910   2009

     More details

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束 加熱長さの影響について Reviewed

    網健行, 梅川尚嗣, 小澤守, 三島嘉一郎, 齋藤泰司

    混相流   Vol.22 No.4 394-402   2008.12

     More details

  • Void Distribution around a Distributor Nozzle of Fluidized Bed Reviewed

    UMEKAWA Hisashi, HOSHIKAWA Yusuke, TSUJI YOUHEI, FURUI SHUJI, OZAWA Mamoru, TAKENAKA Nobuyuki

    Neutron Radiography 8   313-321   313 - +   2008

     More details

    Language:English   Publishing type:Research paper (international conference proceedings)   Publisher:DESTECH PUBLICATIONS, INC  

    Fluidized-bed has high heat transfer performance, and then this technology is used in fluidized-bed boilers, such as PFBC (Pressurized Fluidized-bed Combustors), CFBC (Circulating Fluidized-bed Combustor) boilers. In these boilers, distributors are equipped at the bottom, and fluidized-gas is injected into the fluidized-bed through these distributors. Thus the arrangement and structure of the distributor strongly depend on the movement of fluidized-bed material and also depend on the performance of the fluidized-bed boiler. Thus, the design of the distributors is a very important factor in the design of fluidized-bed boilers. But, these designs are normally decided by empirical methods, and the detail is decided by trial and error. In this investigation the void distribution around the cap type distributor, which is widely used in commercial fluidized-bed boilers, was visualized by using thermal neutron radiography. In the experiment a cap type distributor was set at the bottom of the 150mmX140mmX578mm fluidized-bed, and the CT-processing was also applied to obtain the three dimensional void distribution around the distributor. As it resulted, three-dimensional void propagation after the injecting from the tuyere holes could be clearly visualized. The results are compared by using the two-dimensional experimental apparatus, and the effect of the three dimensional structure is discussed.

    Web of Science

    researchmap

  • Investigation on Two-phase Flow Dynamics with Discrete Bubble Model Reviewed

    AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru, SHOJI Masahiro

    Thermal Science&Engineering   Vol.15 No.4 197-209 ( 4 )   197 - 209   2007.10

     More details

    Language:Japanese   Publisher:The Heat Transfer Society of Japan  

    Kansai University Research Grants 2005-2006

    DOI: 10.11368/tse.15.197

    CiNii Books

    researchmap

    Other Link: http://hdl.handle.net/10112/5954

  • Pattern Dynamics Simulation of Void Wave Propagation Reviewed

    M.Ozawa, H.Umekawa, T.Ami, M.Shoji(Kanagawa Univ.)

    Multiphase Science and Technology   Vol.19 No.4 ( 4 )   343 - 361   2007

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    Gas-liquid two-phase flow is a typical complex system with intrinsic spatiotemporal fluctuation in phase distribution, pressure drop, heat transfer, and so on, being an important subject left behind after extensive research on two-phase flow dynamics. Previously developed modeling is not appropriate in application to CHF problems at low quality and/or in downward flow. This is mainly because conventional modeling, including two-fluid modeling, is based on the continuous flow hypothesis. The proposed model, represented by the discrete bubble model, consists of a void propagation equation as a global rule and only a limited number of mechanical and geometrical relationships as local rules, i.e., a wake effect, gas compressibility, and a phase redistribution mechanism. Neglecting detailed mechanisms of two-phase flow, the spatiotemporal fluctuations in void fraction and pressure drop are numerically realized within the framework of the pattern dynamics approach.

    DOI: 10.1615/MultScienTechn.v19.i4.30

    Scopus

    researchmap

  • Application of CT-processing to Neutron Radiography Imaging of Fluidized-bed Reviewed

    UMEKAWA Hisashi, S.Furui, M.Ozawa, N.Takenaka

    Particle - Particle Systems Characterization   Vol.23 No.3-4, 272-278 ( 3-4 )   272 - 278   2006.10

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:WILEY-V C H VERLAG GMBH  

    CT-processing is very effective in obtaining 3-dimensional information for industrial instruments, and several trials have also been applied to fluidized-beds. In the CT-processing of fluidized-beds, X-rays are used mainly because they are readily availability. Similar processing can be performed by neutron-rays which penetrate most metals, but not some chemical substances, such as hydrogen, boron, gadolinium, which are opaque to the neutrons. Due to these unique characteristics, neutron radiography can be considered as a suitable visualization method of actual industrial instruments made of metal. Thus, neutron radiography also has significant advantages for the visualization of fluidized-beds. However, neutron radiography requires a nuclear reactor or an accelerator as the neutron source in order to obtain high quality images, which means that the real time CT-processing of multiphase flows by neutron radiography is quite difficult. Consequently, CT-images in this investigation were reconstructed by using time-averaged visualization images. Although time averaging makes the understanding of the void movement difficult, 3-dimensional characteristics of the void fraction propagation in fluidized-beds could be clearly visualized by using test sections with significant non-uniformity of the fluidized-gas distribution.

    DOI: 10.1002/ppsc.200601066

    Web of Science

    researchmap

  • Critical Heat Flux in Non-uniformly Heated Tube under Low-Pressure and Low-Mass-Flux Condition Reviewed

    UMEKAWA Hisashi, KITAJIMA Tesuo, HIRAYAMA Mio, OZAWA Mamoru, MISHIMA Kaichiro, SAITO Yasushi

    Heat Transfer-Asian Research   Vol.35 No.1 47-60   2006.1

     More details

    Kansai University Research Grants

    researchmap

  • Parallel-channel instability in natural circulation system Reviewed

    M.Hirayama, H.Umekawa, M.Ozawa

    Multiphase Science and Technology   Vol.18 No.1 55-83 ( 4 )   305 - 333   2006

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    Recently, regional flow instability in two-phase flow system, i.e. flow fluctuations occurred only in the core region of nuclear reactor or multi-channel region without fluctuation of the total inlet flow, is attracting much interest. This flow instability is a significant problem for the systems from the viewpoint of safety and economy. Many investigations on the flow instabilities have been conducted so far, and respective stability criteria have been proposed, while these investigations focused normally on the one-channel system without flow maldistribution, and the resulting stability criteria are hardly applied to the regional flow instability problems. Thus in the present investigation, we conducted analytical investigation focusing not only on the whole system flow instability but also on the regional flow instability. The stability analysis was performed with lumped-parameter model of parallel boiling channels. Finally the stability criteria for the two types of the flow instabilities and the stability maps were obtained.

    DOI: 10.1615/MultScienTechn.v18.i4.10

    Scopus

    researchmap

  • Heat Transfer and Flow Characteristics of a Non-uniformly Heated Tube under Low Pressure and Low Mass Flux Condition Reviewed

    H.Umekawa, M.Hirayama, T.Kitajima, M.Ozawa, K.Mishima, Y.Saito

    Multiphase Science and Technology   Vol.18 No.1 137-161 ( 4 )   387 - 412   2006

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    In an actual boiling channel, the circumferential heat flux is not uniform. Thus, the understanding of the heat transfer characteristics of non-uniformly heated tube becomes an important design factor for conventional boilers, especially for the compact water-tube boiler with tube-nested combustor. The small compact boiler is operated at low-pressure and low-mass flux condition compared with the large scale boiler, so that the non-uniformity in heat flux may strongly affect the heat transfer characteristics. In this investigation, non-uniform heat flux distribution along the circumferential direction was generated by using Joule heating of SUS304 eccentric tubes. The heated length of test-section was 900mm, inner diameter was 20mm, and outer diameter was 24mm. The eccentricity of the tube was s 0, 0.5, 1.0 and 1.5mm. Corresponding maximum/minimum heat fluxes rations were 1.0, 1.7, 3.0 and 7.0, respectively. Experiments were conducted for upward and downward flows, with system pressures 0.3 and 0.4MPa, mass flux range 10-100kg/m2s and inlet temperatures 30 and 80deg.C. The eccentricity resulted in an increase in the CHF of the upward flow, while the effect was hardly observed in the downward flow. The effect of eccentricity on the CHF was well interpreted by the liquid film redistribution. In this paper, the local heat transfer coefficient along the circumferential direction was also presented.

    DOI: 10.1615/MultScienTechn.v18.i4.40

    Scopus

    researchmap

  • Simplified Flow Instability Analysis of a Natural Circulation System with Parallel Boiing Channels Reviewed

    M.Hirayama, H.Umekawa, M.Ozawa

    Thermal Science&Engineering   Vol.13 No.5   2005.10

     More details

  • Visualization of fluidized bed heat exchanger in upward/downward flow condition by neutron radiography Reviewed

    S.Furui, H.Umekawa, M.Tsuzuki, M.OKURA, M.Ozawa, N.Takenaka

    Nuclear Instruments and Methods in Physics Research -A   Vol.542 Issues1-3, 161-167 ( 1-3 )   161 - 167   2005.4

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE BV  

    Heat transfer characteristics of a fluidized-bed heat exchanger are dominated by the characteristics of bed-material movement, especially, in the neighboring region of the heat transfer tube. In the present experiment, a simulated fluidized-bed heat exchanger model was partitioned into two channels to form an upward and downward flow simultaneously in the same fluidized-bed model. Then the total amount of circulating material was kept at the same value even at the different void fractions between two channels. The flow pattern of bed material was visualized by neutron radiography with introducing tracers into the fluidized bed. The simulated fluidized bed consisted of aluminum plates, and the bed materials were sands of 96% SiO2 (mean particle diameter: 0.154-0.321 mm, density: 2550 kg/m(3)). Bed materials were almost transparent for neutrons. On the contrary, tracer particles of about I mm diameter made of B4C with clay were opaque. Thus, the tracer particles were detected clear enough for PTV (Particle Tracking Velocimetry). The fluidized-bed behavior was then discussed in relation to the heat transfer characteristics around the heated tubes submerged in the bed. (c) 2005 Elsevier B.V. All rights reserved.

    DOI: 10.1016/j.nima.2005.01.094

    Web of Science

    researchmap

  • Quantitative measurement of segregation phenomena in a binary mixture fluidized bed by neutron radiography Reviewed

    H.Umekawa, S.Furui, Y.Oshima, M.Okura, M.Ozawa, N.Takenaka

    Nuclear Instruments and Methods in Physics Research -A   Vol.542 Issues1-3, 219-225 ( 1-3 )   219 - 225   2005.4

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE BV  

    Owing to a wide variety in fluidization properties of particles, segregation phenomena are hardly avoided in industrial fluidized-bed facilities. For the stability and controllability in the operation of such fluidized-beds, understanding of the relevant mechanism of particulate segregation is indispensable. Many factors, such as the difference in particle size, density, shape, and also arrangement of distributors, can be pointed out as the dominant causes for the segregation. Thus, any marking of particles for quantitative measurement may severely influence the segregation characteristic to be measured. But neutron radiography can be used for the quantitative measurement without disturbing the segregation characteristic. For estimating the segregation phenomena, evaluations of the particle fraction and the void fraction are required. For this purpose, two types of radiographies, i.e., X-ray and neutron radiographies were used in this investigation. Experimental results demonstrated the high performance of this method in investigating of segregation phenomena. (c) 2005 Elsevier B.V. All rights reserved.

    DOI: 10.1016/j.nima.2005.01.103

    Web of Science

    researchmap

  • Critical Heat Flux in Non-uniformly Heated Tube under Low-Pressure and Low-Mass-Flux Condition Reviewed

    Hisashi Umekawa, Tetsuo Kitajima, Mio Hirayama, Mamoru Ozawa, Kaichiro Mishima, Yasushi Saito

    Transactions of Japan Society of Mechanical Engineers Ser. B.   Vol.71No.703 pp.939-946 ( 703 )   939 - 946   2005.3

     More details

    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:Japan Society of Mechanical Engineers  

    In an actual boiling channel, e.g. boililer water-tubes, the circumferential heat flux is not uniform. Thus, critical heat flux (CHF) of non-uniformly heated tube becomes an important design factor of conventional boilers, especially for the compact water-tube boiler with tube-nested combustor. The small compact boiler is operated at low-pressure and low-mass flux condition compared with the large scale boiler, thus the redistribution of liquid film will strongly affect on the characteristics of CHF. In this investigation, non uniformly heat flux distribution along the circumferential direction was generated by using the Joule heating of SUS304 tubes which had the wall thickness distribution. The heated length of test-section was 900 mm, inner diameter was 20 mm and outer diameter was 24 mm. The center of the inner tube surface was shifted by ε = 0, 0.5, 1.0, 1.5 mm from the center of the outer tube surface. The heat flux ratio between maximum and minimum heat fluxes of these tubes correspond to 1.0, 1.7, 3.0 and 7.0, respectively. Experimental conditions were as follows
    system pressures were 0.3 and 0.4 MPa, mass flux range were 10-100 kg/m2s, inlet temperatures were 30 and 80 deg. C. The experimental results showed an increase in the critical heat flux by the existence of the redistribution of the flow. These characteristics have been well explained by using the similar concept of Butterworth's spreading model.

    DOI: 10.1299/kikaib.71.939

    Scopus

    researchmap

  • Flow Visualization of Segregation Process in a Fluidized Bed by Neutron Radiography Reviewed

    Shuji Furui, H.Umekawa, K.Hayashi, M.Ozawa, N.Takenaka

    IEEE Transactions on Nuclear Science   Vol.52 No.1 ( 1 )   295 - 298   2005

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC  

    Owing to a wide variety in fluidization properties of particles, segregation phenomena are hardly avoided in industrial fluidized-bed facilities. For the stability and controllability in operation of such fluidized-beds, understanding of the relevant mechanism of particulate segregation is indispensable. This paper describes an experimental observation of the particulate segregation in a binary mixture system visualized successfully by using a neutron radiography (NR). The NR gives real-time information of the segregation process, and this information will be very useful in understanding the segregation mechanism.

    DOI: 10.1109/TNS.2005.844016

    Web of Science

    researchmap

  • Quantitative Flow Visualization of Fluidized-Bed Heat Exchanger by Neutron Radiography Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, FURUI Shuji, HAYASHI Kouichi, TAKENAKA Nobuyuki

    Applied Radiation and Isotopes   Vol.61No.4 pp.715-724 ( 4 )   715 - 724   2004

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:PERGAMON-ELSEVIER SCIENCE LTD  

    Quantitative flow visualization of a gas-solid fluidized-bed installed vertical tube-bank has been successfully conducted using neutron radiography and image processing technique. The quantitative data of void fraction distribution as well as the fluctuation data are presented. The time-averaged void fraction is well correlated by the drift-flux model. The bubbles formed in the bed, rise along the vertical tubes and the observed bubble size is smaller than that in a free bubbling bed without tube-banks. The bubble diameter is well correlated by the modified Mori and Wen's correlation taking into account the pitch of tube arrangement. The bubble rise velocity is also well correlated by applying the drift-flux model. These results are consistent for both bed materials of Geldart's B- and A-particles, while the bubble size is significantly different between two kinds of particles. (C) 2004 Elsevier Ltd. All rights reserved.

    DOI: 10.1016/j.apradiso.2004.03.099

    Web of Science

    researchmap

  • Characteristics of Bed-Material Behavior and Heat Transfer around Vertical Tube Banks in a Fluidized Bed Reviewed

    FURUI Shuji, UMEKAWA Hisashi, TSUZUKI Masakazu, OZAWA Mamoru, TAKENAKA Nobuyuki

    Thermal Science and Engineering   Vol.12 No.5 pp.9-19   2004

     More details

  • 着霜を伴う冷却面近傍に発生するミストの研究 Reviewed

    梅川 尚嗣, 今井寿大, 石原勲, 松本亮介

    日本冷凍空調学会論文集   Vol.21 No.3 pp.55-61   2004

     More details

  • Bubble Behavior in Vertical Tube Banks Installed in a Fluidized Bed Reviewed

    UMEKAWA Hisashi, FURUI Shuji, UMEKAWA Hisashi, HAYASHI Kouichi, OZAWA Mamoru, TAKENAKA Nobuyuki

    Heat Transfer Asian Research   32 ( 8 )   727 - 739   2003.12

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    Fluidized bed combustion is one of the advantageous technologies for coal and/or incineration firing especially with respect to the environmental protection of emissions, such as NOx/SOx. Bed material movement in such a fluidized bed has a prime importance in the heat transfer process. Thus, quantitative measurement of the bed material movement and the void fraction are indispensable for better understanding of the fluidized bed. In this investigation, neutron radiography is applied to visualize the bed material movement in a simulated fluidized bed heat exchanger installed with vertical tubes. Bubble behavior and void fraction profile are obtained by the image processing technique. Bubble movement is highly restrained by these vertical tubes, so that the bubbles rise up along the tube. The bubble diameter is well correlated by the modified Mori and Wen's correlation taking into account the pitch of the tube arrangement. The bubble rise velocity and void fraction are well correlated by applying the drift-flux model. © 2003 Wiley Periodicals, Inc.

    DOI: 10.1002/htj.10127

    Scopus

    researchmap

  • Flow Pattern and Void Fraction Fluctuation in Oscillatory Two-Phase Flow Reviewed

    HIRAYAMA Mio, UMEKAWA Hisashi, OKANO Mitsuhiro, OZAWA Mamoru

    Japanese Jouirnal of Multiphase FLow   Vol.17 No.3 285-295 ( 3 )   285 - 295   2003

     More details

  • Critical Heat Flux Condition Induced by Flow Instabilities in Boiling Channels Reviewed

    M.Ozawa, M.Hirayama, H.Umekawa

    Chemical Engineering & Technology   Vol.25 No.12 1197-1201 ( 12 )   1197 - 1201   2002.12

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:WILEY-V C H VERLAG GMBH  

    Web of Science

    researchmap

  • Boiling Two-Phase Heat Transfer of LN2 Downward Flow in Pipe Reviewed

    UMEKAWA Hisashi, UMEKAWA Hisashi, OZAWA Mamoru, YANO Toshiaki

    Experimental Thermal and Fluid Science   Vol.26/6-7. 627-633 ( 6-7 )   627 - 633   2002

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE INC  

    In the field of the air separation technology, the downward-flow-type system has started operation for the main reboiler-condenser instead of the natural-circulation-type system. The downward-flow-type main reboiler-condenser has an advantage in the cost and the ability compared with the natural-circulation-type. while the estimation of heat transfer characteristics has a significant influence on the system performance, In this study, heat transfer experiments have been conducted by using a downward flow of liquid nitrogen (LN2). The comparison of the heat transfer coefficients with existing correlations is discussed. Estimation methods of the flow rate and the pressure drop are also discussed including the prediction of the flow instability. (C) 2002 Elsevier Science Inc. All rights reserved.

    Web of Science

    researchmap

  • Bubble Behavior in Vertical Tube Banks Installed in a Fluidized Bed Reviewed

    Transactions of Japan Society of Mechanical Engineers Ser. B.   Vol.68.No.676,3432-3438   2002

     More details

  • Bubble Behavior and Void Fraction Fluctuation in Vertical Tube Banks Immersed in a Gas-Solid Fluidized Bed Model Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, UMEKAWA Hisashi, FURUI Shuji, HAYASHI Koucichi

    Experimental Thermal and Fluid Science   Vol.26/6-7, 643-652 ( 6-7 )   643 - 652   2002

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE INC  

    Heat transfer characteristics of tube-banks immersed in a fluidized bed are dominated by the time averaged as well as fluctuating characteristics of fluidized-particle movement especially in the neighboring region of heat transfer tube. Quantitative flow visualization of the fluidized bed installed vertical tube-banks has been successfully conducted using neutron radiography and image processing technique. The quantitative data of void fraction distribution as well as the fluctuation data are presented. The bubbles formed in the bed rise along by the vertical tubes and observed bubble size is smaller than that in a free bubbling bed without tube-banks. The bubble diameter is well correlated by the modified Mori and Wen's correlation. The bubble rise velocity is also well correlated by applying the drift-flux model. These results are consistent for both tested bed materials of Geldard's B- and A- particles, while the bubble size is significantly different between two kinds of particles. (C) 2002 Elsevier Science Inc. All rights reserved.

    Web of Science

    researchmap

  • Visualization of Large-Particle Movement in Fluidized-Bed by Neutron Radiography Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, ONODERA Toshikazu, OKURA Yukio, TAKENAKA Nobuyuki, MATSUBAYASHI Masato

    Nondestructive testing and Evaluation   Vol.16 377-390 ( 2-6 )   377 - 389   2001

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    In fluidized-bed boilers, many kinds of particles, e.g., coal, sand, refuse derived fuel (RDF) and limestone, exist. In such binary systems of particles, the segregation may occur, which harms the combustion and thus heat transfer in bed. The particle that rises up in a fluidized-bed is referred to as "flotsam", and the particle that sinks into a fluidized-bed is referred to as "jetsam". Whether a given particle in a fluidized-bed becomes the flotsam or jetsam depends on many factors, such as the density ratio, size ratio, shape of the particle, fluidization velocity, shape of the gas distributors and the material packing ratio. Owing to these complexities, the segregation phenomenon has not been fully understood. In this paper we describe movements of large particles (38 mm spherical balls) in a fluidized-bed (300 mm width 100 mm depth 700 mm height) obtained by the visualization using neutron radiography. In experiments, tracer particles were mixed into the bed, and particle image velocimetry (PIV) and particle tracking velocimetry (PTV) were used to analyze the movement of the large particles and fluidized-bed materials. Visualization results clearly indicated the interaction among large particles, bed materials and bubbles in the bed.

    DOI: 10.1080/10589750108953092

    Scopus

    researchmap

  • Visualization of Bed-Material Movements around Bubble in a Fixed-bed by Neutron radiography Reviewed

    ONODERA Toshikazu, UMEKAWA Hisashi, OZAWA Mamoru, OKURA Yukio, TAKENAKA Nobuyuki, MATSUBAYASHI Masato

    Nondestructive testing and Evaluation   Vol.16 391-402 ( 2-6 )   391 - 402   2001

     More details

    Language:English   Publishing type:Research paper (scientific journal)  

    A single-bubble movement and induced bed-material movement were fundamental processes in the flow mechanism of a fluidized-bed. A single gas bubble was injected into the fixed-bed with the tracer particles (B4C) and the flow field around the bubble was visualized using neutron radiography. The image processing technique was applied to the visualized images and the velocity field was obtained by using PIV (Particle Image Velocimetry) technique. The result clearly showed bed-material movement around the rising bubble, i.e., the transverse movement at the roof of the bubble, the free fall or downward motion at the side and the upward motion in the bubble wake.

    DOI: 10.1080/10589750108953092

    Scopus

    researchmap

  • CHF in Oscillatory Flow Boiling Channels Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MISHIMA Kaichiro, HIBIKI Takashi, SAITO Yasushi

    IChemE Transactions Part A- Chemical Engineering Research and Design   Vol.79 No.4,389-401 ( A4 )   389 - 401   2001

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:INST CHEMICAL ENGINEERS  

    Recent advanced technologies in boiler manufacturing bring about highly efficient and compact water-tube boilers for gas firing or oil firing. These boilers have very simple water-circulation system, which often brings about flow instabilities followed by critical heat flux, CHF, problems. This paper describes such an oscillatory flow (CHF) at relatively low mass flux and at low pressure. CHF is a decreasing function of the amplitude and period of the flow oscillation, and reaches almost 40 % of the steady state value. When the tube wall is thin, CHF is mainly controlled by the two-phase flow dynamics and is well simulated using a simple lumped-parameter model of boiling channel. At very low mass flux, CHF depends significantly on the how orientation, and is closely related to the flow pattern transition.

    Web of Science

    researchmap

  • 中性子ラジオグラフィによる流動層熱交換器内層材挙動の可視化 Reviewed

    小澤守, 梅川尚嗣, 小野寺俊和, 古井秀治, 竹中信幸

    可視化情報学会誌   Vol.20 No.1 343-346   2000.8

     More details

  • X線ラジオグラフィによる流動層の可視化 Reviewed

    古井秀治, 小澤守, 梅川尚嗣

    可視化情報学会誌   Vol.20 No.1 343-346   2000.8

     More details

  • Visualization of Bubble and Large Particle Movements in a Fluidized-Bed of Binary Mixture of Particles Reviewed

    UMEKAWA H., ONODERA T., OZAWA M., TAKENAKA N.

    Japanes Journal of Multiphase Flow   Vol.14 No.4, 451-455 ( 4 )   451 - 465   2000

     More details

    Language:Japanese   Publisher:THE JAPANESE SOCIETY FOR MULTIPHASE FLOW  

    Fluidized-bed combustion systems are composed of many kinds of particles with a variety of sizes, e.g. coal, sand, RDF, limestone etc. In such a binary system of particles, the segregation, if occurs, may harm the combustion, mixing and heat transfer in the bed, depending on the particle movement. The particle movement or circulation in the fluidized-bed depends on many factors, such as the density ratio, size ratio, shape of particle, fluidization velocity. Owing to the difficulty of flow visualization, such particle movement has not been fully understood so far. This paper describes large-particle movement obtained by the flow visualization using neutron radiography. Tracer particles mixed into the fluidized particles indicated clearly bubbles and the cloud behavior around the bubble. Image processing, i.e. PIV and PTV, gives rather clear understanding on the interaction between the large particle, emulsion and/or cloud behavior in the bed.

    DOI: 10.3811/jjmf.14.451

    CiNii Books

    researchmap

    Other Link: http://hdl.handle.net/10112/4940

  • Quantitative Flow Visualization of Fluidized-Bed under normal and down-flow-mode operations by neutron radiography Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, TAKENAKA Nobuyuki, MATSUBAYASHI Masato

    Experiments in Fluids   28, 413-424 ( 5 )   413 - 424   2000

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:SPRINGER  

    Heat transfer characteristics of tube-banks immersed in a fluidized-bed is dominated by the time-averaged as well as statistical characteristics of bed-material movement, especially, in the neighboring region of heat transfer tube. The neutron radiography and image processing technique have been successfully applied to the visualization of flow field and quantitative measurement of void fraction in the bed. This quantitative visualization technique is verified as a useful means in understanding the flow behavior and thus the heat transfer mechanisms.

    Web of Science

    researchmap

  • Visualization of Bed Material Movement in a Simulated Fluidized-Bed Heat Exchanger by Neutron Radiography Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, TAKENAKA Nobuyuki, MATSUBAYASHI Masato

    Nuclear Instruments and Methods in Physics Research -A   Vol.424 No.1, 77-83 ( 1 )   77 - 83   1999

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE BV  

    The bulk movement of fluidized bed material was visualized by neutron radiography by introducing tracers into the bed materials. The simulated fluidized bed consisted of aluminum plates, and the bed material was sand of 99.7% SiO(2) (mean diameter: 0.218 mm, density: 2555 kg/m(3)). Both materials were almost transparent to neutrons. Then the sand was colored by the contamination of the sand coated by CdSO(4). Tracer particles of about 2 mm diameter were made by the B(4)C, bonded by the vinyl resin. The tracer was about ten times as large as the particle of fluidized bed material, but the traceability was enough to observe the bed-material bulk movement owing to the large effective viscosity of the fluidized bed. The visualized images indicated that the bubbles and/or wakes were important mechanism of the behavior of the fluidized bed movement. (C) 1999 Elsevier Science B.V. All rights reserved.

    Web of Science

    researchmap

  • Scaling Parameter of CHF under Oscillatory Flow Conditions Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, MITSUNAGA Tamotsu, MISHIMA Kaichiro, HIBIKI Takashi, SAITO Yasushi

    Heat Transfer Asian Research   Vol.28 No.6, 541-550 ( 6 )   541 - 550   1999

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Scripta Technica Inc  

    Critical heat flux (CHF) is reduced by flow oscillations. The reduction of CHF is significantly influenced by flow oscillation period and amplitude, heat capacity of test tube, and mean inlet mass flux. A scaling parameter of the temperature response of the tube wall was derived based on a lumped-parameter model of the tube wall's heat capacity. When this scaling parameter was applied to CHF under flow oscillations, the experimental data were successfully correlated.

    DOI: 10.1002/(SICI)1523-1496(1999)28:6<541::AID-HTJ10>3.0.CO;2-E

    Scopus

    researchmap

  • Scaling Paramenter of CHF under Oscillatory Flow Condition Reviewed

    Transactions of Japan Society of Mechanical Engineers Ser. B.   Vol.64 No.617 161-166   1998

     More details

  • Flow Pattern and Heat Transfer in Tube Banks of a Simulated Fluidized-Bed Heat Exchanger Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MATSUDA Takeshi, TAKENAKA Nobuyuki, MATSUBAYASHI Masato

    JSME Int.   41-3, 720-726 ( 3 )   720 - 726   1998

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:JAPAN SOC MECHANICAL ENGINEERS  

    A simulated fluidized-bed heat exchanger with tube banks was visualized using a neutron radiography system. Observed flow pattern indicated an importance of the tube arrangement. Heat transfer experiment, conducted simultaneously, indicated a close relationship between the heat transfer and flow pattern. The staggered arrangement with relatively small pitch has a potential of high heat transfer performance.

    Web of Science

    researchmap

  • Dryout and Post-Dryout Heat Transfer in a Natural Circulation Loop of Liquid Nitrogen Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, ISHIDA Naoki

    Heat Transfer- Japanese Research   26-7, pp.449-458   1997.11

     More details

  • Large-Particle Movement and Drag Coefficient in a Fluidized Bed Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MATSUDA Takeshi, TAKENAKA Nobuyuki, MATUBAYASHI Masato, TSURUNO Akira

    Heat Transfer Japanese Research   Vol.26 No.1,54-67   1997

     More details

  • 3-D Temperature Measurement of Natural Convection by Image Processing Technique Reviewed

    UMEKAWA Hisashi

    Visualization Society of Japan   Vol.17 No.64 41-45   1997

     More details

  • Large Particle Movement and Drag Coefficient in a Fluidzed Bed Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MATSUDA Takeshi, TAKENAKA Nobuyuki, MATSUBAYASHI Masahito, TSURUNO Akira

    Transactions of Japan Society of Mechanical Engineers Ser. B.   Vol.62 No.601 185-192 ( 601 )   3413 - 3420   1996

     More details

    Language:Japanese   Publisher:The Japan Society of Mechanical Engineers  

    Flow visualization of the behavior of a large particle in a fluidized bed was conducted using neutron radiography. The large particle moved according to the bed materials, especially in the wake of a bubble. When the density of the large particle was high, the particle moved with a velocity different from that of bubble, and in some cases the particle moved downward through a bubble. When the density was low enough, the particle moved on the surface of the bubble wake. The drag force of the large particle immersed in the fluidized bed was measured. The drag force increased with increase in the volumetric gas flux as well as with increase in the particle diameter. The drag coefficient was derived and was well correlated on the basis of a two-phase model and experimentally determined effective viscosity of the bed materials.

    DOI: 10.1299/kikaib.62.3413

    CiNii Books

    researchmap

    Other Link: http://hdl.handle.net/10112/4702

  • Void Fraction Profile in Tube-banks of a Simulated fluidized-bed Heat Exchanger Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, MATSUDA Takeshi, TAKENAKA Nobuyuki, TSURUNO Akira, MATSUBAYASHI Masato

    Nuclear Instruments and Methods in Physics Research -A   377-1, 144-147 ( 1 )   144 - 147   1996

     More details

    Language:English   Publishing type:Research paper (scientific journal)   Publisher:ELSEVIER SCIENCE BV  

    Flow visualization of cross-flow tube-banks in a simulated fluidized-bed was conducted by using the neutron radiography system of JRR-3M. Applying the image processing technique to the visualized image, the void fraction profile in the tube-bank was obtained. The observed flow pattern and the void fraction profile demonstrate the importance of the tube arrangement in fluidized-bed hear exchangers.

    Web of Science

    researchmap

  • Critical Heat Flox under Flow Oscillation in a Natural Circulation Loop of Liquid Nitrogen Reviewed

    Japanese Journal of Multiphase Flow   Vol.11 No.1 56-65   1996

     More details

  • Dryout in a Boiling Channel under Oscillatory Flow Condition Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, MIYAZAKI Akira, MISHIMA Kaichiro, HIBIKI Takashi

    Trans.Jpn. Soc. Mech. Eng.   Vol.61 No.583, 1048-1054   1995

     More details

  • CHF in a Boiling Channel under Oscillatory Flow Condition Reviewed

    UMEKAWA Hisashi, OZAWA Mamoru, MIYAZAKI Akira

    Advances in Multiphase Flow 1995 Elsevier   497-506   497 - 506   1995

     More details

    Language:English   Publishing type:Research paper (international conference proceedings)   Publisher:ELSEVIER SCIENCE PUBL B V  

    Web of Science

    researchmap

  • Dryout in a Boiling Channel under Oscillatory Flow Condition

    UMEKAWA Hisashi, OZAWA Mamoru, MIYAZAKI Akira, MISHIMA Kaichiro, HIBIKI Takashi

    JSME Int. J. B   39-2,412-418   1995

     More details

  • Dryout under Oscillatory Flow Condition in Vertical and Horizontal Tubes Reviewed

    OZAWA Mamoru, UMEKAWA Hisashi, YOSHIOKA Yohji, TOMIYAMA Akio

    Int.J.Heat Mass Transf.   36-16, 4076-4078 ( 16 )   4076 - 4078   1993

     More details

    Language:English   Publisher:PERGAMON-ELSEVIER SCIENCE LTD  

    Web of Science

    researchmap

  • Heat Transfer in a Fin-Tube Type Heat Exchanger with Multiple Inlet Ports. -Numerical Simulation and Thermal Flow Visualization under Cooling Condition- Reviewed

    Trans. of the JAR   Vol.10 No.3 401-411   1993

     More details

  • Flow Pattern in a Fin-Tube Type Heat Exchanger with Multiple Inlet Ports - Numerical Simulation and Flow Visualization under Isothermal Condition Reviewed

    Tran. of the JAR.   Vol.9 No.2 57-67   1992

     More details

  • Study on Heat and Mass Transfer under Frosting Condition-1st Report Reviewed

    UMEKAWA Hisashi

    Trans. of the JAR   Vol.8 No.3 173-178   1991

     More details

▼display all

Books

  • Flow Boiling

    梅川 尚嗣( Role: Joint author)

    Fundamentals of Thermal and Nuclear Power Generation(Eds. Y.Koizumi, T.Okawa, S.Mori), Elsevier  2021 

  • 中性子イメージングカタログ/中性子施設ハンドブック

    梅川尚嗣( Role: Joint author)

    公益社団法人 日本アイソトープ協会  2018.10 

     More details

  • Convectice Boiling under Unstable Flow Conditions

    ( Role: Contributor)

    Elsevier・Boiling -Reserch and Advances-  2017  ( ISBN:9780081010105

     More details

  • 中性子ラジオグラフィを用いた熱交換器への着霜の評価

    松本亮介, 吉村智也(D), 梅川尚嗣, 網健行, 伊藤大介(京大炉), 齊藤 泰司(京大炉)( Role: Joint author)

    Isotope News  2015.6 

     More details

  • For the Discussion of the Nuclear Power

    Hisashi UMEKAWA( Role: Sole author)

    2013.4 

     More details

  • エネルギー変換論入門

    小澤守, 竹中信幸, 梅川尚嗣, 浅野等, 松本亮介, 村川英樹( Role: Contributor)

    コロナ社  2013.4 

     More details

  • JSMF25th Anniversary Discussion by the Recent Presidents -The Role of the Society, Past, Present and Future-

    Masanori Aritomi, Masanori Naito, Manabu Iguchi, Akira Yabe, Kaichiro Mishima, Michio Sadatomi, Hiroshige Kikura, Hisashi Umekawa( Role: Contributor)

    Japanese Journal of Multiphase Flow  2012.12 

     More details

  • 演習 工業熱力学

    小澤守, 梅川尚嗣, 松本亮介, 網健行( Role: Contributor)

    電気書院  2011.11 

     More details

  • 熱移動論入門

    竹中信幸(神戸大), 小澤守, 梅川尚嗣, 浅野等(神戸大), 松本亮介( Role: Contributor)

    コロナ社  2008.11 

     More details

▼display all

Presentations

  • 規則充填物内気液対向二相流の3次元流動特性

    平賀龍哉(D), 梅川尚嗣, 網健行, 飯倉寛(JAEA), 栗田圭輔(JAEA)

    2023.8 

     More details

  • 上昇流および下降流における液膜挙動の観察

    神谷 優太(D), 網 健行, 梅川 尚嗣

    2023.3 

     More details

    Venue:大阪  

    researchmap

  • 規則充填物内気液対向二相流の3次元流動特性

    平賀 龍哉(D), 梅川 尚嗣, 網 健行, 飯倉 寛(JAEA), 栗田 圭輔(JAEA)

    2023.3 

     More details

    Venue:大阪  

    researchmap

  • マイクロチャネル熱交換器の可視化定量評価

    梅川 尚嗣

    2023.1 

     More details

  • マイクロチャネル熱交換器の可視化定量評価

    舩倉 陸(D), 梅川 尚嗣, 網 健行, 斎藤 泰司(KURNS), 伊藤 大介(KURNS)

    2023.1 

     More details

  • Influence of Luminance Scatter in Darkbox for Visualization byusing Neutron Radiography

    H.Umekawai, Y.Kamiya(D), K.Akiyama(D), T.Ami, N.Odaira(KURNS), D.Ito(KURNS), Y.Saito(KURNS), M.Matsubayashi(JAEA)

    2023 

     More details

  • 特殊流路内の気液二相流のボイド率分布計測

    梅川尚嗣, 平賀龍哉 (D), 永冨大世(D), 舩倉陸 (D), 網健行, 飯倉寛 (JAEA), 栗田圭輔 (JAEA)

    2023 

     More details

  • サーペンタイン管における限界熱流束

    井窪 瞬(D), 網 健行, 梅川 尚嗣

    2022.10 

     More details

    Venue:東京  

    researchmap

  • 規則充填物でのフラッディング特性

    梅川 尚嗣, 高橋脩人, 平賀龍哉, 網健行, 飯倉寛(JAEA), 栗田圭輔(JAEA)

    2022.8 

     More details

    Venue:Zoom(東京)  

    researchmap

  • Visualization of Dynamic Flow Maldistributino in a Microchannel Heat Exchangger

    H.Umekawa, T.Ami, R.Funakura(D), K.Orido(D), K.Akiyama(D), Y.Saito(KURNS), D.Ito(KURNS), N.Odaira(KURNS)

    2022 

     More details

  • 特殊流路内の気液二相流のボイド率分布計測

    梅川 尚嗣, 網 健行, 平賀龍哉 (D), 舩倉陸 (D), 飯倉寛(JAEA), 栗田圭輔(JAEA)

    2022 

     More details

  • JRR-3 と KUR における気液二相流研究に関する検討

    梅川 尚嗣, 舩倉 陸(D), 秋⼭ 慶⼦(D), 平賀⿓哉(D)

    2021.12 

     More details

  • 非均一加熱下におけるマイクロチャネル熱交換器の伝熱特性

    舩倉 陸(D), 阪井 広幸(D), 梅川 尚嗣, 網 健行, 齋藤 泰司(KURNS), 伊藤 大介(KURNS)

    2021.10 

     More details

    Venue:Zoom(佐賀)  

    researchmap

  • 非均一加熱下のマイクロチャネル熱交換器内伝熱流動特性

    阪井 広幸(D), 舩倉 陸(D), 梅川 尚嗣, 網 健行, 斎藤 泰司(京大複合研), 伊藤 大介(京大複合研), 大平 直也 (京大複合研)

    2021.1 

     More details

  • Quantaively Visulaization of a Microchannel Heat Exchanger under Nonuniformly Heated Condition

    H.Umekawa, T.Ami, H.Sakai(D), R.Funakura(D), Y.Saito(KURNS), D.Ito(KURNS)

    2021 

     More details

  • Visualization of a Microchannel Heat Exchanger under Non-uniormly Heated Condition

    H.Sakai(D), H.Umekaaw, T.Ami, Y.Saito(KURNS), D.Ito(KURNS)

    2020.8 

     More details

  • 沸騰流動系可視化定量評価の新展開

    阪井 広幸(D), 折戸 敬一郎(D), 舩倉 陸(D), 藤原 弘樹(D), 鈴木 直翔(D), 陰山 拓実(D), 小畑 公作(D), 柴田 滉平(D), 梅川 尚嗣, 網 健行,, 斎藤 泰司(KURI), 伊藤 大介(KURI)

    2019.12 

     More details

  • Quantitative Measurement of Reflooding Process by Using Neutron Radiography

    Hisashi Umekawa, Kei Saito(D), Hiroki Fujiwara(D), Hiroyuki Sakai(D), Takeyuki Ami, Yasushi Saito(KURNS), Daisuke Ito (KURNS)

    2019.11 

     More details

    Venue:Zhenjiang, China.  

    researchmap

  • 垂直下降流における沸騰開始点の特性

    亀田貴俊(D), 網健行, 梅川尚嗣

    第24回動力・エネルギー技術シンポジウム  2019.6 

     More details

    Venue:東京  

    researchmap

  • 定常中性子イメージングへの期待-大学研究者からの立場で-

    梅川尚嗣

    2019.3 

     More details

    Venue:東京  

    researchmap

  • Quantitative Dynamic Measurement of Void Fraction

    H.Umeakwa, T.Ami, K.Saito(D), Y.Kawazoe(D), K.Obata(D), K.Shibata(D), H.Sakai(D), Y.Saito(KURNS), D.Ito(KURNS)

    2019 

     More details

  • KUR中性子ラジオグラフィによる沸騰二相流研究の展望

    梅川尚嗣

    中性子イメージング専門研究会  2018.12 

     More details

    Venue:京都大学複合科学研究所  

    researchmap

  • 並列管の構造が流動安定性へ与える影響

    利光 敦(D), 小畑 公作(D), 網 健行, 梅川 尚嗣, 小澤 守, 山田 明(三菱重工),, 中拂 博之, 渡辺 悠太

    熱工学コンファレンス 2018  2018.10 

     More details

    Venue:富山  

    researchmap

  • 低圧条件下における垂直下降流の限界熱流束-管内径および加熱長さの影響-

    川副 祥規(D), 網 健行, 梅川 尚嗣, 小澤守

    熱工学コンファレンス 2018  2018.10 

     More details

    Venue:富山  

    researchmap

  • 原子力に対する認識の変遷

    梅川尚嗣

    2018年度日本機械学会年次大会  2018.9 

     More details

    Venue:吹田  

    researchmap

  • 中性子ラジオグラフィによる再冠水時の逆環状流の可視化

    齋藤 啓(D), 網 健行, 梅川 尚嗣, 齊藤 泰司(京大複合研), 伊藤 大介(京大複合研)

    2018年度日本機械学会年次大会  2018.9 

     More details

    Venue:吹田  

    researchmap

  • エネルギーについて考える-知って欲しいこと,知りたいこと- いい電気と悪い電気~電気の質

    梅川尚嗣

    2018年度日本機械学会年次大会  2018.9 

     More details

    Venue:吹田  

    researchmap

  • 4本並列沸騰管における流動安定性に対する入口抵抗の付加位置の影響

    小畑 公作(D), 利光 敦(D), 網 健行, 梅川 尚嗣, 小澤 守, 山田 明(MHI),, 中拂 博之(MHI), 渡辺 悠太(MHI)

    第23回動力・エネルギー技術シンポジウム  2018.6 

     More details

    Venue:宇部  

    researchmap

  • 鉛直下降流における限界熱流束時の液膜流量評価

    柴田 滉平(D), 北中 匠(D), 網 健行, 梅川 尚嗣, 小澤 守

    第23回動力・エネルギー技術シンポジウム  2018.6 

     More details

    Venue:宇部  

    researchmap

  • The flow characteristics in a distillation column. Influence of clearance of packing and physical property of working fluid

    2018.3 

     More details

    Venue:Nagasaki, Japan  

    researchmap

  • Classification of Critical Heat Flux Mechanisms for Downward Flow

    2018.3 

     More details

    Venue:Nagasaki, Japan  

    researchmap

  • Trial Measurement of Void Fraction in Boiilng Channel

    H.Umekawa, T.Ami, M.Kitagawa, T.Kitanaka, Y.Kawazoe, K.Saito, Y.Saito(IRNSK), D.Ito(IRNSK)

    KURRI PROGRESS REPORT 2017  2018 

     More details

    http://www.rri.kyoto-u.ac.jp/PUB/report/PR/ProgRep2017/ProgRep2017.html

    researchmap

  • Trial Measurement of Void Fraction in Boiilng Channel

    H.Umekawa, T.Ami, M.Kitagawa, T.Kitanaka, Y.Kawazoe, K.Saito, Y.Saito(IRNSK), D.Ito(IRNSK)

    2018 

     More details

  • 原子力に関する意識の変遷と教育

    梅川尚嗣

    第28回東海伝熱セミナー  2017.9 

     More details

  • 規則充填物におけるフラッディング特性

    北川真佑帆(D), 久保田貴大(D), 網健行, 梅川尚嗣

    2017.8 

     More details

    Venue:調布  

    researchmap

  • Prediction Model of Critical Heat Flux for Vertical Downward Flow

    Yoshiki Kawazoe, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    2017.6 

     More details

    Venue:Toyohashi JAPAN  

    researchmap

  • 原子力発電所の再稼働と市民の安心-学会の役割

    小泉安郎, 宮口治衛(IHI), 永田徹也(日立GEニュークリア・エナジー), 白井孝治(電力中央研究所), 森下正樹(JAEA), 岡本孝司(東大), 梅川尚嗣, 工藤和彦(九大), 近藤智恵子(長崎大)

    日本機械学会2016年度年次大会  2016.9 

     More details

    Venue:伊都  

    researchmap

  • Estimation of the Water Behavior in Defrosting Process by Using Neutron Radiography

    Ryosuke Matsumoto, Tomoya Yoshimura, Hisashi Umekawa, Takeyuki Ami, Daisuke ITO(KURRI), Yasushi Saito

    2016.9 

     More details

    Venue:Kobe,Japan  

    researchmap

  • Flow Characteristics of Counter-current Two-ohase Flow in Structured Packings -Influence of Clearance of Packings-

    Takahiro Kubota, Takeyuki Ami, Hisashi Umekawa

    2016.8 

     More details

    Venue:Kyoto, Japan  

    researchmap

  • Critical Heat Flux for Downward Flow in a Vertical Mini-Channel -The Case of 20mm in innner Diameter-

    Tomoyuki Harada, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    日本機械学会熱工学コンファレンス2015講演論文集  2015.10 

     More details

    Venue:Osaka, Japan  

    researchmap

  • Influence of Heating Length on Entrainment in a Boiling Two-Phase Flow -Indirect ealuation based on the liquid filmflow measurement-

    Ryuga Nakano(D), Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    日本機械学会熱工学コンファレンス2015講演論文集  2015.10 

     More details

    Venue:Osaka, Japan  

    researchmap

  • 技術が支える持続可能な社会とエネルギーインフラ(日本の現状と今後の展望、リスクにどう向き合うのか) エネルギー教育の現状と事例

    梅川尚嗣

    日本機械学会年次大会講演資料  2015.9 

     More details

    Venue:札幌  

    researchmap

  • Dryout in a Natural Circulation Loop under Density Wave Oscillation

    Hisashi UMEKAWA, Takeyuki Ami, Mamoru Ozawa

    Japan-U.S. Seminar on Two-Phase Flow Dynamics  2015.5 

     More details

  • 水平管内の粒子流動特性に関する研究

    竹内高穂, 藤井大二郎, 網健行, 梅川尚嗣

    日本機械学会関西支部第90期講演会  2015.3 

     More details

  • 体流束条件下における水平沸騰二相流の伝熱・流動特性

    西岡真優, 大高竜太, 網健行, 梅川尚嗣, 小澤守

    日本機械学会関西支部第90期講演会  2015.3 

     More details

  • 機械学会から見たkURへの期待

    梅川尚嗣

    京都大学原子炉実験所『将来計画』短期研究会 報告書  2015.2 

     More details

    Venue:大阪  

    researchmap

  • 規則充填物内気液二相流の流動特性

    吉岡翔太(D), 網健行, 梅川尚嗣, 小澤守

    熱工学コンファレンス2014  2014.11 

     More details

  • 自然循環ループにおける再冠水仮定の伝熱・流動特性

    河井拓哉, 湯本一貴, 網健行, 梅川尚嗣, 小澤守

    熱工学コンファレンス2014  2014.11 

     More details

  • The Influence of the Heating Condition on the Void Fraction of Boiling Channel

    Hisashi UMEKAWA, Syota Nakamura(D), Syota Fujiyoshi(D), Takeyuki Ami, Mamoru OZAWA

    10th World Conference on Neutron Radiography  2014.10 

     More details

    Venue:Grindelwald CH  

    researchmap

  • Quantitative estimation of frost formation on plate-fin tube Heat exchanger by neutron radiography

    Ryosuke Matsumoto, Tomoya Yoshimura, Hisashi Umekawa, Takeyuki Ami, Disuke Ito(KURRI), Yasushi Saito(KURRI)

    Proceedings of the 15th International Heat Transfer Conference  2014.8 

     More details

    Venue:Kyoto, Japan  

    researchmap

  • Effect of Flow Pattern on Critical Heat Flux

    Takeyuki Ami, Goshi Yamashina(D), Hisashi Umekawa, Mamoru Ozawa

    Proceedings of the 15th International Heat Transfer Conference  2014.8 

     More details

    Venue:Kyoto, Japan  

    researchmap

  • Heat transfer and flow characteristics of liquid nitrogen in natural circulation loop with parallel tubes

    Ikki Yumoto, Takaho Takeuchi, Takuya Kawai, Ryuma Fujiwara, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    JSMF Symposium on Multiphase Flow 2014  2014.7 

     More details

  • Type of Critical Heat Flux for Downward Flow in a vertical Tube

    Takayuki Harada, Syota Fujiyoshi, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA, Yasushi Saito, Daiskue Ito

    The 19th National Symposium on Power and Energy Systems(SPES 2014)  2014.6 

     More details

  • Evaluation of Convective Boiling in Oscillatory Flow

    2013.12 

     More details

  • Characteristics of the Void Fraction under aForced Convective Flow Boiling

    Hisasshi Umekawa, Takeyuki Ami, Kazunari Sakakura(D), Syota NaKamura(D), Syota Fujiyoshi(D), Goshi Yamashina(D), Yasusi Saito(KURRI), Daisuke Ito(KURRI), Yuji Kawabata(KURRI)

    KURRI Progress Reoort2012  2013.11 

     More details

  • Influence of the Flow Pattern on Critical Heat Flux

    Goshi Yamashina, Noriko Nakamura, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    JSMF  2013.8 

     More details

    Venue:Nagano, Japan  

    researchmap

  • Report on the Great East Japan Earthquake DisasterMechanical Enginnering Volume

    Joint Editional Committee for the Report on the Great East Japan Earthquake Disaster

    Maruzen  2013.7 

     More details

  • Effect of Taylor Bubble Wake on the Trailing Bubble in a Inclined Upward Flow

    Noriko Nakamura, Yoshimune Hirose, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA

    JSME  2013.6 

     More details

    Venue:Chiba, Japan  

    researchmap

  • 流動層吹き出しのノズル周りの伝熱・流動特性

    鶴岡秀則(D), 三井健佑(B), 松永涼佑(B), 網健行, 梅川尚嗣, 小澤守

    関西支部第88期定時総会講演会  2013.3 

     More details

    Venue:大阪  

    researchmap

  • 下降流におれる伝熱・流動特性-中性子ラジオグラフィの適用-

    阪倉一成(D), 中村祥太(D), 網健行, 梅川尚嗣, 小澤守, 伊藤大介(京大炉), 齋藤泰司(京大炉)

    関西支部第88期定時総会講演会  2013.3 

     More details

    Venue:大阪  

    researchmap

  • Influence of the Flow Pattern on Critical Heat Flux

    Goshi Yamashina, Takaho Takeuchi, Noriko Nakamura, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    Proceedings of Thermal Engineering Conference '12  2012.11 

     More details

    Venue:Kumamoto  

    researchmap

  • 中性子ラジオグラフィを用いた着霜現象の可視化

    吉村智也(D), 松本亮介, 梅川尚嗣, 網健行, 齋藤泰司(京大炉)

    熱工学コンファレンス(ギャラリーコレクション)  2012.11 

     More details

    Venue:熊本  

    researchmap

  • Visualization of Frosting Phenomena by Using Neutron Radiography

    2012.10 

     More details

  • Quantitative Evaluation of Void Wave Propagatino in Oscillatory Flow by Using Neutron Radiography

    KURRI Progress Report 2011  2012.10 

     More details

  • Oil-water mixture in horizontal mini-channel

    6th Japanese-European Two-Phase Flow Group Meeting  2012.9 

     More details

    Venue:Kumamoto  

    researchmap

  • Qualitatively measurement of void fraction under oscillatory flow condition

    6th Japanese-European Two-Phase Flow Group Meeting  2012.9 

     More details

    Venue:Kumamoto  

    researchmap

  • Quantitative Evaluation of Frosting Phenomena by Using Neutron Radiography

    2012.9 

     More details

  • Flow Characteristics of Oil-Water Mixture in Horizontal Mini-Channel (Influence of Inner Diameter)

    AMI Takeyuki, Kouhei Awata, Hisashi Umekawa, Mamoru Ozawa

    JSMF Annual Meeting 2012  2012.8 

     More details

    Venue:Kashiwa  

    researchmap

  • Interactino between consecutive bubbles-Effect of tube inclination-

    Yoshimune Hirose, Noriko Nakamura, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA

    JSMF Annual Meeting 2012  2012.8 

     More details

    Venue:Kashiwa  

    researchmap

  • Pattern Dynamics Approach to Two-Phase Flow Dynamics -In Memory of Professor Seikan Ishigai, the Founder of the First Japan-U.S. Seminar on Two-Phase flow Dynamics-

    2012.7 

     More details

  • Pseudo dynamic visualization of boiling two-phase flow under oscillatory flow condition

    2012.6 

     More details

  • Quantitative Measurement of Void Fraction in a Forced Convective Flow Boiling by using Neutron Radiography

    2012.6 

     More details

  • Quantitative Evaluation of Void Wave Propagation in Oscillatory Flow by using Neutron Radiography

    2012.6 

     More details

  • CHF in a circumferentially nonuniformly heated tube under low-pressure and low-mass-flux conditionInfluence of Inclined angles under high heat flux condition

    2012.6 

     More details

  • CHF in a circumferentially nonuniformly heated tube under low-pressure and low-mass-flux condition Influence of Inclined angles under high heat flux condition

    2012.6 

     More details

  • Heat transfer of particle convection in Fluidized-bed

    2012.6 

     More details

  • Heat and Flow Characteristics around a Nozzle in Fluidized-bed

    The Eighth KSME-JSME Thermal and Fluids Engineering Conference  2012.3 

     More details

    Venue:Incheon, Korea  

    researchmap

  • Dryout of Counter-Current Two-Phase Flow under Diabatic Condition

    The Eighth KSME-JSME Thermal and Fluids Engineering Conference  2012.3 

     More details

    Venue:Incheon, Korea  

    researchmap

  • Quantitiative Evaluation of Void Fraction on Boiling Two-phase Flow in a Tube by using Neutron Radiography

    2012.1 

     More details

    Venue:Osaka, Japan  

    researchmap

  • Quantitative Evaluation of Frosting Phenomena on Fin-tube Heat Exchanger

    2012.1 

     More details

    Venue:Osaka, Japan  

    researchmap

  • Boiling heat transfer and flow characteristics of liquid nitrogen in helically coiled tube

    22nd International symposium on Transport Phenomena  2011.11 

     More details

    Venue:Delft  

    researchmap

  • Oil-water mixture in horizontal mini-channel

    22nd International symposium on Transport Phenomena  2011.11 

     More details

    Venue:Delft  

    researchmap

  • Boiling Heat Transfer and Flow Characteristics in Helically Coiled Tube with Natural Circulation Loop

    Takayuki TSURUNO, Yoshihiro IMAKURA, Takeyuki AMI, Hisashi UMEKAWA, Mamoru OZAWA

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    There is still not enough knowledge of thermal-fluid characteristics in helically coiled tube under flow instability condition. In this investigation, experiment was conducted by using a natural circulation loop with liquid nitrogen as working fluid. The test section was helically coiled tube and had 4 mm in inner tube diameter, 100 mm in coil diameter and 3150 mm in heated length. The experimental condition was inlet throttle valve Kin = 540, 1076, 2065, and system pressure pex = 0.3, 0.5 MPa. As an experimental result, a inlet flow rate, boiling heat transfer and critical heat flux had been evaluated including post-dryout condition.

    researchmap

  • Critical Heat Flux in a Circumferentially Non-Uniformly Heated Tube under Low-Pressure and Low-Mass-Flux Condition(Influence of Inclined Angles under High Heat Flux Condition)

    Takuya Hirose, Kyohei Kajisako, Kazunari Sakakura, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    researchmap

  • Critical Heat Flux in a Circumferentially Non-Uniformly Heated Tubeunder Low-Pressure and Low-Mass-Flux Condition(Influence of Inclined Angles under High Heat Flux Condition)

    Takuya Hirose, Kyohei Kajisako, Kazunari Sakakura, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    Critical Heat Flux (CHF) in a non-uniformly heated tube under inclined upward flow conditions is very important factor in designing actual boiling systems. However, only a few investigations on the CHF have been conducted under these conditions. Consequently, in the series of investigations, the experimental study on the CHF of non-uniformly heated tube was conducted with 900 mm and 1800 mm in heated length under the inclined condition. In this study, the CHF experiment was conducted with 450 mm in heated length under several inclination angles, i.e. 15, 30, 45 and 90 degree. The characteristic of CHF is decided by the relation between the gravity and the liquid film lift up, and these effects have been able to be categorized by using the modified Froude number well.

    researchmap

  • Critical Heat Flux of Counter-Current Two-Phase Flow (Effect of Subcooled Liquid Film)

    Ayaka Fujiwara, Takuya Suzuki, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    Dryout of counter-current two-phase flow is widely observed in the actual chemical and/or industrial systems. In case of the diabatic counter-current two-phase flow, the upward gas increases with the liquid film evaporation along the heating tube and flooding strongly affects the dryout of counter-current two-phase flow. In this investigation, the dryout experiment was conducted with the counter-current two-phase flow consisted of the free falling liquid film and upward gas flow. The obtained dryout characteristics were strongly influenced on the degree of inlet subcoooling, and are classified into three groups on the basis on the dryout mechanism.

    researchmap

  • Particle Convective Heat transfer in Fluidized Bed(Evaluation of Thermal Contact Resistance at the Wall)

    Yusuke Tomioka, Takeyuki Ami,, Hisashi Umekawa, Mamoru Ozawa

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    To understand the heat transfer characteristics in fluidized bed, the particle convection becomes the most important factor in the bed. In this investigation, the heat transfer experiment under a forced particle convection was conducted by using the cylinder-shaped fluidized with stirrer, and we measured a temperature in the bed. In this experiment, several sizes of particles (dp=0.2mm, 0.4mm, 1.0mm) were used. As a result, there was a sharp temperature drop in the first layer from the heating surface. And the experimental results were estimated by using a simple heat transfer model with effective thermal conductivity, particle-gas heat transfer coefficient and thermal contact resistance.

    researchmap

  • Oil-Water Mixture in Horizontal Mini-Channels

    Kohei Awata, Takeyuki Ami, Hisashi Umekawa, Mamoru Ozawa

    2011.10 

     More details

    Venue:Hamamatsu, Japan  

    In this research, flow pattern and pressure drop characteristics of kerosene-water two phase flow in horizontal mini-channel was investigated. The tube diameter was 0.53 mm, and it was made from pyrex glass. The volumetric fluxes of each liquids were set between 0.05 and 0.6 m/s. The several flow patterns were observed in mini-channel, i.e. Droplet flow, Slug flow, Slug-Annular flow, Annular flow, Parallel flow and Kerosene slug flow. The transition of flow pattern has been explained by using Weber number of each phase. The pressure drop has shown a good agreement with Lockhart-Martinelli correlation, moreover the adaptability of the moving film model to the estimation of pressure in the slug flow regime has been confirmed.

    researchmap

  • 中性子ラジオグラフィを用いた管内強制流動沸騰系のボイド率評価

    梅川尚嗣

    関西支部第12回秋期技術交流フォーラム 気液二相流技術懇話会資料  2011.10 

     More details

    Venue:大阪  

    researchmap

  • Quantitaive Measurement of Liquid-film Movement under Forced Convective Boiling Condition by using Neutron Radiography

    KURRI Progress Report 2010  2011.10 

     More details

  • 連続スラグ気泡間の相互干渉について 離散気泡モデルによる数値シミュレーションの評価

    中村典子(D), 廣瀬由宗(D), 網健行, 梅川尚嗣, 小澤守

    日本混相流学会年会講演会講演論文集  2011.9 

     More details

    Venue:京都  

    researchmap

  • Characteristics of Frost Flormation on Fin-tube Heat Exchanger

    Hiroki Ryuoku, Ryouske Matsumoto, Tomoya Yoshimura, Hisashi UMEKAWA, Takeyuki Ami

    2011 JSRAE Annual Conference  2011.9 

     More details

    Venue:Tokyo, Japan  

    researchmap

  • Quantitatively Measurement of Void Fraction under Forced Convective Boiing Condition by using Neutron Radiography

    UMEKAWA Hisashi, TANIGUCHI Hitoshi, NAKAMURA Syota, AMI Takeyuki, SAITO Yasushi

    ASME-JSME-KSME Fluids Engineering Conference2011  2011.7 

     More details

  • Influence of a Flow Obstacle on boiling Two-Phase Flow

    AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru

    Proceedings of the ASME 2011 Power Conference (POWER 2011) and the International Conference on Power Engineering 2011 (ICOPE-11)  2011.7 

     More details

  • 流動層内吹き出しノズル周りの伝熱・流動特性

    鶴岡秀則, 網健行, 梅川尚嗣, 小澤守

    第48回日本伝熱シンポジウム講演論文集  2011.6 

     More details

    Venue:岡山  

    researchmap

  • 中性子ラジオグラフィによる強制流動沸騰場の定量評価

    梅川尚嗣

    日本機械学会熱工学部門相変化研究会  2011.5 

     More details

    Venue:岡山  

    researchmap

  • Advanced Power Generation System and Related Thermal Engineering Problems

    OZAWA Mamoru, MATSUMOTO Ryousuke, UMEKAWA Hisashi

    Proc. 8th ASME-JSME Thermal Engineering Joing Conf  2011.3 

     More details

  • 気液対向二相流における限界熱流束

    鈴木拓哉, 網健行, 梅川尚嗣, 小澤守

    日本機械学会関西支部第86期定時総会講演会  2011.3 

     More details

    Venue:大阪  

    researchmap

  • 小口径管におけるフラッディング

    西本貴晶, 藤原綾夏, 高枩諒, 網健行, 梅川尚嗣, 小澤守

    日本機械学会関西支部第86期定時総会講演会  2011.3 

     More details

    Venue:大阪  

    researchmap

  • 中性子ラジオグラフィを用いた円管内沸騰二相流のボイド率定量評価

    谷口斉, 網健行司, 梅川尚嗣, 小澤守, 斎藤泰司

    日本機械学会関西支部第86期定時総会講演会  2011.3 

     More details

    Venue:大阪  

    researchmap

  • 中性子ラジオグラフィを用いた円管内沸騰二相流のボイド率評価

    谷口斉

    中性子イメージング専門研究会  2011.1 

     More details

  • 流動層内における粒子対流熱伝達の評価 粒子径の影響

    富岡佑介, 網健行, 梅川尚嗣, 小澤守

    日本機械学会熱工学コンファレンス2010講演論文集  2010.10 

     More details

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束特性 高熱流束条件下での管傾斜の影響

    廣瀨拓哉, 阪倉一成, 網健行, 梅川尚嗣, 小澤守

    日本機械学会熱工学コンファレンス2010講演論文集  2010.10 

     More details

  • Flooding in a small diameter tube

    AMI Takeyuki, NISHIMOTO Takaaki, UMEKAWA Hisashi, OZAWA Mamoru

    Japan-UK mini-Seminar on Multiphase Flow 2010  2010.9 

     More details

  • Interaction between Consecutive Large Bubbles in a Vertical Slug Flow

    NAKAMURA Noriko, AMI Takeyuki, UMEKAWA Hisashi, OZAWA Mamoru

    Japan-UK mini-Seminar on Multiphase Flow 2010  2010.9 

     More details

  • 連続スラグ気泡の相互干渉に関する評価

    中村典子, 網健行, 梅川尚嗣, 小澤守

    日本混相流学会年会講演会2010講演論文集  2010.7 

     More details

  • らせん管内液体窒素沸騰二相流における伝熱・流動特性

    網健行, 中村典子, 鶴野嵩敬, 樋口 徹, 梅川尚嗣, 小澤守

    日本混相流学会年会講演会2010講演論文集  2010.7 

     More details

  • 流動障害物に設置による沸騰二相流への影響

    網健行, 林慎二, 梅川尚嗣, 小澤守

    第15回動力エネルギー技術シンポジウム講演論文集  2010.6 

     More details

  • 小口径管におけるフラッディング 供試管材質の影響

    西本貴晶, 民谷尚紀, 網建行, 梅川尚嗣, 小澤守

    第15回動力エネルギー技術シンポジウム講演論文集  2010.6 

     More details

  • CHF in a Non-Uniform Circumferential Heating Tube under Low-Pressure and Low-Mass-Flux Condition

    UMEKAWA Hisashi, HOTTA Kazunari, AMI Takeyuki, OZAWA Mamoru, MISHIMA Kaichiro, SAITO Yasushi

    7th International Conference on Multiphase Flow ICMF2010  2010.6 

     More details

  • 低圧・低質量流束条件下における周方向非均一加熱管の限界熱流束 加熱長さの影響

    網健行, 廣瀬拓哉, 堀田一成, 梅川尚嗣, 松本亮介, 小澤守, 三島嘉一郎, 斎藤泰司

    第47回日本伝熱シンポジウム講演論文集  2010.5 

     More details

  • 強せん断力場における液体窒素沸騰二相流の伝熱流動特性

    並川大輔, 網 健行, 梅川尚嗣, 小澤 守

    日本機械学会関西支部第85期定時総会講演会  2010.3 

     More details

  • らせん管内液体窒素沸騰二相流の伝熱・流動特性

    樋口 徹, 網 健行, 梅川尚嗣, 小澤 守

    日本機械学会関西支部第85期定時総会講演会  2010.3 

     More details

  • 低圧・低質量流束条件下における周方向非均一加熱管の伝熱・流動特性 加熱長さの影響

    堀田一成, 廣瀨拓哉, 二階堂尚志, 網 健行, 梅川尚嗣, 小澤 守

    日本機械学会関西支部第85期定時総会講演会  2010.3 

     More details

  • Heat Transfer and Flow Pattern of Boiling Flow CO2 in Mini-channels

    HARA Takashi, AMI Takeyuki, UMEKAWA Hisashi, MATUSMOTO Ryosuke, OZAWA Mamoru, ISHIHARA Isao

    2010 International Symposium on Next-Generatino Air Conditioning and Refrigeration Technology  2010.2 

     More details

  • Restriction of Critical Heat Flux by Critical Flow Condition in Capillary Tube

    Hisashi UMEKAWA, Mamoru Ozawa, Takeshi Sanami

    ASME2003 1st Internatinal Conference on Microchannels and Minichannels  2003.4 

     More details

    Venue:Rochester  

    researchmap

▼display all

Works

  • 進化する機械「沸かすということ」

    梅川尚嗣

    2011.10

     More details

Awards

  • 部門貢献表彰

    2024.11   日本機械学会動力エネルギーシステム部門   JSME Series in Thermal and Nuclear Power Generation出版を通じての技術継承活動

    JSME Series in Thermal, Nuclear Power, Generation, 出版ワーキンググループ

     More details

  • 学術賞

    2009.6   日本伝熱学会  

     More details

    Country:Japan

    researchmap

Research Projects

  • 日本原子力研究開発機構(日本原子力研究所)

      More details

    Grant type:Competitive

    researchmap

  • Kyoto University Research Reactor Institute

      More details

    Grant type:Competitive

    researchmap

  • 三菱重工

      More details

  • 大陽日酸 (日本酸素)

      More details

    Grant type:Competitive

    researchmap

  • 三菱重工

      More details

    Grant type:Competitive

    researchmap

  • 大阪大学

      More details

    Grant type:Competitive

    researchmap

  • 大阪ガス

      More details

    Grant type:Competitive

    researchmap

▼display all

Social Activities

  • 財)放射線利用振興協会・中性子利用技術移転推進プログラム コーディネーター

    2007 - 2010

     More details

Devising educational methods

  • 講義で使用したパワーポイント等については原則として、CEASで公開している。さらに伝熱工学、熱力学については都度レポートを課し学生の理解度を確認している。 また定期的に実施する講義内試験については、本年度より本人の答案をコピーして返却する方法を試みており本人が自分の理解度を確認出来る手法を取っている。 授業評価については回収率に疑問を感じるWebではなく、講義時間内に紙ベースで実施している。

Teaching materials

  • 熱力問題集、伝熱工学教科書 その他、説明用パワーポイント、説明用プリント等

Teaching method presentations

  •  特になし

Special notes on other educational activities

  •  特になし